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Journal Articles

Validation of core cooling capability analysis in Monju during guillotine pipe break at primary heat transport system

Yamada, Fumiaki; Arikawa, Mitsuhiro*; Fukano, Yoshitaka

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

In sodium-cooled fast reactor, since the coolant does not need to be pressurized, a pipe break due to the internal pressure does not occur physically. For safety margin in Japanese prototype fast breeder reactor (Monju), the guillotine pipe break accident, i.e., loss of integrity (LOPI) has been analyzed as an extreme assumption for beyond design basis accidents (B-DBAs) in the licensing application for the permit. The cooling capability of the core was re-evaluated in this paper during a large-scale, more specifically guillotine pipe break at the primary heat transport system (PHTS) in Monju, newly considering the following latest findings: (a) Experimental data on sodium boiling in fuel assemblies, (b) Actual PHTS pump coast-down characteristics, and (c) Transient burst test data on irradiated fuel claddings. The analysis models were the validated and simulations were re-performed also using the actual Monju data such as the response time to the trip signals, etc. As a result, it was clarified that the ratio of failed fuel claddings does not exceed around 3% of all of fuel assemblies, as in the past licensing analysis. The safety has been reconfirmed to be secured without significant core damage even under an extreme assumption of a double-ended guillotine pipe break at the PHTS in Monju.

Journal Articles

Creep rupture properties of a Ni-Cr-W superalloy in air environment

; Tsuji, Hirokazu; Shindo, Masami; Nakajima, Hajime

Journal of Nuclear Materials, 246(2-3), p.196 - 205, 1997/00

 Times Cited Count:17 Percentile:77.48(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Creep rupture properties of Ni-Cr-W superalloy in air environment

Kurata, Yuji; Tsuji, Hirokazu; Shindo, Masami; Nakajima, Hajime

JAERI-Research 96-052, 48 Pages, 1996/10

JAERI-Research-96-052.pdf:2.71MB

no abstracts in English

Journal Articles

Long-term creep properties of Hastelloy XR in simulated high-temperature gas-cooled reactor helium

Kurata, Yuji; *; ; Shindo, Masami; Nakajima, Hajime; *

Journal of Nuclear Science and Technology, 32(11), p.1108 - 1117, 1995/11

 Times Cited Count:3 Percentile:36.75(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Long-term creep and rupture behavior of Hastelloy XR in simulated high-temperature gas-cooled reactor helium

Kurata, Yuji; *; ; Shindo, Masami; Nakajima, Hajime; *

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 36(2), p.149 - 156, 1995/07

no abstracts in English

JAEA Reports

Creep behaviour of Hastelloy XR in simulated high-temperature gas-cooled reactor helium

Kurata, Yuji; *; ; Shindo, Masami; Nakajima, Hajime; *

JAERI-Research 95-037, 42 Pages, 1995/06

JAERI-Research-95-037.pdf:2.04MB

no abstracts in English

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